• Title/Summary/Keyword: plant requirements

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Roads to Construct and Re-build Plant Microbiota Community

  • Kim, Da-Ran;Kwak, Youn-Sig
    • The Plant Pathology Journal
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    • v.38 no.5
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    • pp.425-431
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    • 2022
  • Plant microbiota has influenced plant growth and physiology significantly. Plant and plant-associated microbes have flexible interactions that respond to changes in environmental conditions. These interactions can be adjusted to suit the requirements of the microbial community or the host physiology. In addition, it can be modified to suit microbiota structure or fixed by the host condition. However, no technology is realized yet to control mechanically manipulated plant microbiota structure. Here, we review step-by-step plant-associated microbial partnership from plant growth-promoting rhizobacteria to the microbiota structural modulation. Glutamic acid enriched the population of Streptomyces, a specific taxon in anthosphere microbiota community. Additionally, the population density of the microbes in the rhizosphere was also a positive response to glutamic acid treatment. Although many types of research are conducted on the structural revealing of plant microbiota, these concepts need to be further understood as to how the plant microbiota clusters are controlled or modulated at the community level. This review suggests that the intrinsic level of glutamic acid in planta is associated with the microbiota composition that the external supply of the biostimulant can modulate.

Modeling the Present Probability of Urban Woody Plants in the face of Climate Change (기후변화에 따른 도시 수종의 기후 적합성 평가모델 - 서울시를 대상으로 -)

  • Kim, Yoon-Jung;Lee, Dong-Kun;Park, Chan
    • Journal of the Korean Society of Environmental Restoration Technology
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    • v.16 no.1
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    • pp.159-170
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    • 2013
  • The effect of climate change on urban woody plants remains difficult to predict in urban areas. Depending on its tolerances, a plant species may stay and survive or stay with slowly declining remnant populations under a changing climate. To predict those vulnerabilities on urban woody plants, this study suggests a basic bioclimatic envelop model of heat requirements, cold tolerance, chilling requirements and moisture requirements that are well documented as the 'climatic niche'. Each component of the 'climatic niche' is measured by the warmth index, the absolute minimum temperature, the number of chilling weeks and the water balance. Regarding the utility of the developed model, the selected urban plant's present probabilities are suggested in the future climate of Seoul. Both Korea and Japan's thermal thresholds are considered for a plant's optimal climatic niche. By considering the thermal thresholds of these two regions for the same species, the different responses observed will reflect the plant's 'hardening' process in a rising climate. The model illustrated that the subpolar plants Taxus cuspidata and Ulmus davidiana var. japonica are predicted to have low suitability in Seoul. The temperate plants Zelkova serrata and Pinus densiflora, which have a broad climatic niche, exhibited the highest present probability in the future. The subtropical plants Camellia japonica and Castanopsis cuspidata var. sieboldii may exhibit a modest growth pattern in the late 21C's future climatic period when an appropriate frost management scheme is offered. The model can be used to hypothesize how urban ecosystems could change over time. Moreover, the developed model can be used to establish selection guidelines for urban plants with high levels of climatic adaptability.

Systematic Generation of PLC-based Design from Formal Software Requirements (정형 소프트웨어 요구사항으로부터 PLC 디자인의 체계적 생성)

  • Yoo Junbeom;Cha Sungdeok;Kim Chang Hui;Song Deokyong
    • Journal of KIISE:Software and Applications
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    • v.32 no.2
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    • pp.108-118
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    • 2005
  • The software of the nuclear power plant digital control system is a safety-critical system where many techniques must be applied to it in order to preserve safety in the whole system. Formal specifications especially allow the system to be clearly and completely specified in the early requirements specification phase, therefore making it a trusted method for increasing safety. In this paper, we discuss a systematic method, which generates PLC-based FBD programs from the requirements specification using NuSCR, a formal requirements specification method. This FBD programs takes an important position in design specification. The proposed method can reduce the possible errors occur in the manual design specification, and the software development cost and time. To investigate the usefulness of our proposed method, we introduce the fixed set-point rising trip example, a trip logic of BP in DPPS RPS, which is presently being developed at KNICS.

Bioassays of Plant Hormones and Plant Growth Regulating Substances II. Abscisic Acid and Brassinolide (식물홀몬 및 생장조절물질의 생물검정기술 II. Abscisic Acid 및 Brassinolide)

  • 최충돈
    • KOREAN JOURNAL OF CROP SCIENCE
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    • v.34 no.s01
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    • pp.16-25
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    • 1989
  • A bioassay is a test system using a living organism (in whole or in part) to determine the presence or relative potency of chemical substances. The development and uses of bioassay are intimately linked to the discovery and characterization of the major classes of plant hormones. An application of this relationship is helpful for understanding the concept of plant hormones as well as the use of bioassay. And plant bioassay have been development and employed not only for the discovery and characterization of the biological activity of plant growth regulators but also have served several important secondary roles. The ideal bioassay should possess the characteristic of high specificity. great sensitivity. short response time, low cost and ease of obtaining plant material. acceptable ease of manipulation, and minimal space and equipment requirements.

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Architectural model driven dependability analysis of computer based safety system in nuclear power plant

  • Wakankar, Amol;Kabra, Ashutosh;Bhattacharjee, A.K.;Karmakar, Gopinath
    • Nuclear Engineering and Technology
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    • v.51 no.2
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    • pp.463-478
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    • 2019
  • The most important non-functional requirements for dependability of any Embedded Real-Time Safety Systems are safety, availability and reliability requirements. System architecture plays the primary role in achieving these requirements. Compliance with these non-functional requirements should be ensured early in the development cycle with appropriate considerations during architectural design. In this paper, we present an application of system architecture modeling for quantitative assessment of system dependability. We use probabilistic model checker (PRISM), for dependability analysis of the DTMC model derived from system architecture model. In general, the model checking techniques do not scale well for analyzing large systems, because of prohibitively large state space. It limits the use of model checking techniques in analyzing the systems of practical interest. We propose abstraction based compositional analysis methodology to circumvent this limitation. The effectiveness of the proposed methodology has been demonstrated using the case study involving the dependability analysis of safety system of a large Pressurized Water Reactor (PWR).

Training Requirements for Control Room Operators of an Advanced Nuclear Power Plant

  • Park, Hong Joon;Park, Geun Ok;Kim, Sa Kil;Byun, Seong Nam
    • Journal of the Ergonomics Society of Korea
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    • v.32 no.1
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    • pp.107-115
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    • 2013
  • Objective: The aim of this study is to identify the training requirements of new nuclear power plant by a comprehensive literature review. Background: The design of instrumental and control systems for New NPP is applied fully digitalized systems. For example, soft-control, large display panels(LDP), and an advanced alarm system were applied to the APR-1400 or SMART. Method: The NUREG-0711 and international guideline of training program was analyzed from the following four phases of SAT(Systemic Approach to Training): Analysis, Design, Development, Implementation and Evaluation. Results: To identify the requirement of training program, 'Feedback' phase was considered and each phase of SAT was classified. Conclusion: A more systematic requirement of training program is needed which considers the computerized system was applied to the new NPP. Application: The results of the publishing can be useful for standardization of the systematic training program for the operators of NPP.

Cybersecurity Threats and Responses of Safety Systems in NPPs (원전 안전계통의 사이버보안 위협 및 대응)

  • Jung, Sungmin
    • Journal of Korea Society of Digital Industry and Information Management
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    • v.16 no.1
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    • pp.99-109
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    • 2020
  • In the past, conservative concepts have been applied in terms of the characteristic of nuclear power plants(NPPs), resulting in analog-based equipment and closed networks. However, as digital technology has recently been applied to the design, digital-based facilities and communication networks have been used in nuclear power plants, increasing the risk of cybersecurity than using analog-based facilities. Nuclear power plant facilities are divided into a safety system and a non-safety system. It is essential to identify the difference and cope with cybersecurity threats to the safety system according to its characteristics. In this paper, we examine the cybersecurity regulatory guidelines for safety systems in nuclear power plant facilities. Also, we analyze cybersecurity threats to a programmable logic controller of the safety system and suggest cybersecurity requirements be applied to it to respond to the threats. By implementing security functions suitable for the programmable logic controller according to the suggested cybersecurity requirements, regulatory guidelines can be satisfied, and security functions can be extended according to other system requirements. Also, it can effectively cope with cybersecurity attacks that may occur during the operation of nuclear power plants.

Transient Analysis of the CANDU-9 480/SEU Reactor (CANDU-9 480/ SEU 원자로의 과도변화해석)

  • J. C. Shin;Park, J. H.;K. N. Han;H. C. Suk
    • Nuclear Engineering and Technology
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    • v.27 no.5
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    • pp.687-700
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    • 1995
  • The thermal-hydraulic transient analysis of the proposed CANDU-9 plant was peformed. Several major transients ore analyzed if they meet the heat transport system design requirements. The proposed heat transport system configuration and the preliminary sizes of system equipment are justified by analysis in terms of the fuel integrity and the high system pressure limit during transients. The compliance with AECB R-77 requirements for CANDU-9 reactor was estimated. The analysis results showed that for each postulated accident the peak pressure values in the reactor headers are within the acceptance criteria given in ASME code requirements and the fuel overheating is prevented. One pump start-up during the reactor start-up operation was analyzed to investigate the How reversal through the fuel channel, which is specific in the proposed CANDU-9 plant.

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SPSF : Smart Plant Safety Framework based on Reliable-Secure USN (차세대 USN기반의 스마트 플랜트안전 프레임워크 개발)

  • Jung, Ji-Eun;Song, Byung-Hun;Lee, Hyung-Su
    • Journal of The Institute of Information and Telecommunication Facilities Engineering
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    • v.9 no.3
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    • pp.102-106
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    • 2010
  • Recently process industries from oil and gas procedures and mining companies to manufactures of chemicals, foods, and beverages has been exploring the USN (Ubiquitous Sensor Networks) technology to improve safety of production processes. However, to apply the USN technology in the large-scale plant industry, reliability and security issues are not fully addressed yet, and the absence of the industrial sensor networking standard causes a compatibility problem with legacy equipment and systems. Although this situation, process industry such as energy plants are looking for the secure wireless plant solution to provide detailed, accurate safety monitoring from previously hard-reach, unaccordable area. In this paper, SPSF (Smart Plant Safety Framework based on Reliable-Secure USN) is suggested to fulfill the requirements of high-risk industrial environments for highly secure, reliable data collection and plant monitoring that is resistant to interference. The SPSF consists of three main layers: 1) Smart Safety Sensing Layer, 2) Smart Safety Network Layers, 3) Plant Network System Layer.

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A Study on EPRI TR-106439 for Digital Indicator of Nuclear Power Plant (원전용 디지털 인디케이터의 검증 규정 EPRI TR-106439에 관한 고찰)

  • Bae, Chang-Ho;Lee, Dong-Hee;Kim, Kyu Ro;Jang, Joong Soon
    • Journal of Applied Reliability
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    • v.14 no.4
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    • pp.248-255
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    • 2014
  • Nuclear power plants may use commercial grade items if they can pass special tests or inspections, which is called Commercial Grade Item Dedication (CGID). Digital items, however, should follow EPRI TR-106439 to be applied to nuclear power plants. This paper explains the scheme and requirements of the EPRI TR-106439 and introduces some guidelines. Firstly, in order to clarify requirements of the EPRI TR-106439, code interpretation is performed. And through case study of digital indicator, limitations of EPRI TR-106439 are mentioned, and improvement direction is proposed.